KR20080051980A - Tester for heating pipe of steam generater - Google Patents

Tester for heating pipe of steam generater Download PDF

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KR20080051980A
KR20080051980A KR1020060123891A KR20060123891A KR20080051980A KR 20080051980 A KR20080051980 A KR 20080051980A KR 1020060123891 A KR1020060123891 A KR 1020060123891A KR 20060123891 A KR20060123891 A KR 20060123891A KR 20080051980 A KR20080051980 A KR 20080051980A
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lens
pipe
steam generator
vertical
tube
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KR1020060123891A
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Korean (ko)
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KR100855117B1 (en
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이경선
백승근
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한전케이피에스 주식회사
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N21/00—Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
    • G01N21/84—Systems specially adapted for particular applications
    • G01N21/88—Investigating the presence of flaws or contamination
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Analytical Chemistry (AREA)
  • Thermal Sciences (AREA)
  • General Health & Medical Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Immunology (AREA)
  • Pathology (AREA)
  • Chemical & Material Sciences (AREA)
  • Biochemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Health & Medical Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

A tester for a heating pipe of a steam generator is provided to execute horizontal motion and vertical motion by including a hinge device and a pulling device. A tester for a heating pipe of a steam generator includes a checking lens(37), a lens support pipe(38), a pipe body, and a pulling guide rope(34). The checking lens checks the surface of the heating pipe around a flow rate distribution pipe in every nook and corner. The lens support pipe supports the lens. The pipe body receives the lens support pipe including the lens and includes a horizontal unit(31) and a vertical unit(32) which are coupled to each other with a hinge(33). The pulling guide rope allows the vertical unit of the pipe body to be horizontal and vertical.

Description

원자력발전용 증기발생기의 전열관 표면 검사장치{Tester for heating pipe of steam generater}Heat pipe surface inspection device for nuclear generator steam generators {Tester for heating pipe of steam generater}

도 1 은 일반적인 증기발생기의 일부절결 도면,1 is a partial cutaway view of a general steam generator,

도 2 는 도 1 의 요부 수직 단면도,2 is a vertical cross-sectional view of the main part of FIG. 1;

도 3 은 증기발생기의 작동 설명도면,3 is an explanatory view of the operation of the steam generator,

도 4 는 도 2 의 A-A선 단면도,4 is a cross-sectional view taken along the line A-A of FIG.

도 5 는 증기발생기에 사용되는 유량분배관의 사시도,5 is a perspective view of a flow distribution pipe used for the steam generator,

도 6a 내지 도6c 는 본 발명의 사용상태 설명도,6a to 6c are explanatory diagrams of the use state of the present invention;

도 7 은 본 발명의 요부 사시도,7 is a perspective view of main parts of the present invention;

도 8 은 본 발명의 요부 단면도이다.8 is a sectional view of principal parts of the present invention.

도면의 주요 부분에 대한 부호의 설명Explanation of symbols for the main parts of the drawings

1;입구노즐 2;외부하우징 3;전열관 4;관판 5;출구노즐 6;관지지판 7;핸드홀 8;유량분배관 8-1;유량분배관홀 10;증기발생기 20;래퍼 21;증기배출구 22;통공 30;검사장치 31;수평부 32;수직부 32-1;로프고정구 33;힌지 34;가이드로프 35;가이드체 36;눈금부 37;렌즈 38;렌즈지지관 1; Inlet nozzle 2; External housing 3; Heat pipe 4; Tube plate 5; Outlet nozzle 6; Tube support plate 7; Hand hole 8; Flow distribution pipe 8-1; Flow distribution pipe hole 10; Steam generator 20; Wrapper 21; Steam outlet 22; Through hole 30; Inspection device 31; Horizontal part 32; Vertical part 32-1; Rope fastener 33; Hinge 34; Guide rope 35; Guide body 36; Scale 37; Lens 38; Lens support tube

본 발명은 원자력발전용 증기발생기의 전열관 표면 검사장치에 관한 것으로, 전열관의 표면을 유량배분관을 지나 구석 구성 찾아 검사할 수 잇도록 수직 및 수평부와 수직부의 상태를 조정하는 힌지부와, 상태 조정용 당김로우프를 포함하는 원자력발전용 증기발생기의 전열관 표면 검사장치에 관한 것이다.The present invention relates to a heat pipe surface inspection device for a steam generator for nuclear power generation, the hinge portion for adjusting the vertical and horizontal portion and the state of the vertical portion so that the surface of the heat pipe passing through the flow distribution pipe and find the corner configuration, and The present invention relates to a heat pipe surface inspection device for a steam generator for nuclear power generation including an adjustment pull rope.

일반적으로, 원자력발전소에서 증기발생기는 증기터빈과 발전기로부터 전력을 생산하는 데 필요한 증기를 발생시키는 가장 중요한 핵심기기 중의 하나이다.In general, steam generators in nuclear power plants are one of the most important key devices for generating the steam required to generate power from steam turbines and generators.

여기서, 증기의 발생과정을 살펴보면, 원자로를 통과하면서 가열된 1차수가 관로를 따라 증기발생기 전열관 내부를 흐르고 이 전열관 외부로 공급되는 2차수가 전열관의 외부로 교차하면서 전열관의 관벽을 사이에 두고 1차수와 2차수가 열교환을 통해 1차수는 폐회로의 관로를 따라 다시 원자로로 순환되고 2차수는 증기로 변환된다.Here, the steam generation process, the primary water heated while passing through the reactor flows through the steam generator heat pipe along the pipeline and the secondary water supplied to the outside of the heat pipe crosses the outside of the heat pipe, with the pipe wall of the heat pipe interposed therebetween 1 Through the heat exchange of the order and the second order, the first order is circulated back to the reactor along the pipeline of the closed circuit and the second order is converted to steam.

한편, 상기 증기발생기 내부를 순환하는 1차수는 원자로를 통과하면서 가열과 방사능에 오염이 되고 가압기에 의해 가압된 방사능을 띈 고온 고압수로서 전열관이 파열되면 2차수를 오염시켜 방사능 누출을 초래할 수 밖에 없다. 따라서 원자력발전소에서 증기발생기는 방사능을 격리하는 1차 방위설비이다.On the other hand, the primary water circulating in the steam generator is contaminated with heating and radioactivity while passing through the reactor, and the high temperature and high pressure water ruptures the radiation pressurized by the pressurizer when the heat pipe rupture contaminates the secondary water to cause radioactive leakage none. Therefore, steam generators in nuclear power plants are the primary defense facilities to isolate radioactivity.

도 1은 일반적인 증기발생기를 나타낸 도면이고, 도 2는 도 1의 증기발생기의 정단면도이고, 도 3 은 증기발생원리를 나타내는 단면도로, 증기발생기(10)는 1차 계통 의 원자로냉각재가 들어오는 입구노즐(1)과, 열교환이 이루어지도록 하는 전열관(3)과, 상기 입구노즐(1)을 통해 들어오는 원자로냉각재를 바깥쪽에 있는 2착계통 냉각수에 열을 전달하는 출구노즐(5) 등으로 구성된다. 전열관(3)은 관판(4)위에 안치되며, 안치된 전열관(3)은 일정 수직 높이 간격마다 관지지판(6)으로 지지되도록 하고, 하단의 관지지판(6)과 관판(4)사이에는 도너츠판 상의 유량배분판(8)을 안치시켜 전열판(3)을 지지하고 도록 한다. 전열판을 지지하는 다수의 일정 수직 간격의 관지지판(6)및 전열관(3)은 하부가 개방되고 상단에 증기배출구(21)를 가지는 래퍼(20)를 결합하고, 래퍼(20)는 물을 외부하우징(2) 내벽을 따라 아래로 공급받고, 공급받은 물은 전열관에 의하여 증기를 발생되어 위로 배출하는 기능을 한다.1 is a view showing a general steam generator, Figure 2 is a front sectional view of the steam generator of Figure 1, Figure 3 is a cross-sectional view showing the steam generation principle, the steam generator 10 is the inlet in which the reactor coolant of the primary system enters Nozzle (1), heat transfer pipe (3) for heat exchange, and an outlet nozzle (5) for transferring heat to the reactor coolant on the outside of the reactor coolant coming through the inlet nozzle (1). . The heat transfer tube 3 is placed on the tube plate 4, and the heat transfer tube 3 is supported by the tube support plate 6 at regular vertical height intervals, and a donut is disposed between the tube support plate 6 and the tube plate 4 at the bottom. The flow distribution plate 8 on the plate is settled to support the heat transfer plate 3. A plurality of constant vertically spaced tube support plate 6 and the heat transfer tube 3 supporting the heat transfer plate are combined with a wrapper 20 having a lower opening and a steam outlet 21 at an upper end thereof, and the wrapper 20 externally drains water. It is supplied downward along the inner wall of the housing 2, and the supplied water functions to generate steam by the heat transfer tube and discharge it upward.

이와 같이 구성된 증기발생기는, 1차 계통의 원자로 냉각재는 입구노즐(1)로 들어와서 다수의 전열관(튜브)(3) 안쪽으로 흐르면서 출구노즐(5)을 통과하여 바깥쪽에 있는 이차계통 냉각수에 열을 전달하고 이때 증기가 생성되게 한다.In the steam generator configured as described above, the reactor coolant of the primary system enters the inlet nozzle 1 and flows into the plurality of heat pipes (tubes) 3 and passes through the outlet nozzle 5 to heat the secondary system coolant outside. To produce steam.

여기서, 증기발생기(10)에서 원자로 냉각재가 흐르는 부분을 1차측, 급수 및 증기가 흐르는 부분을 2차측 이라 한다. 2차계통은 주증기계통, 터빈 계통, 복수 및 급수계통 등으로 구성된다.Here, the portion where the reactor coolant flows in the steam generator 10 is referred to as a primary side, and a portion in which water supply and steam flow is referred to as a secondary side. The secondary system consists of main steam system, turbine system, plural and feed water system.

따라서, 증기발생기(10) 2차측에서 생성된 수증기는 주증기관을 따라 이동하여 터빈을 회전시킨다.Therefore, the steam generated at the secondary side of the steam generator 10 moves along the main steam engine to rotate the turbine.

그러나, 종래의 증기발생기는 증기를 만들기 위해 2차 측에 공급되는 2차수는 여과와 화학처리를 통해 공급되지만 관로 내부를 순환하면서 여러 가지 경로를 통해 발 생한 이물질과 슬러지를 동반하여 증기발생기 내부로 유입되어, 관판(tube sheet)과 관지지판(tube support plate)에 침전되거나 전열관 외벽에 들러붙게 되어 전열효과를 저하시키거나 손상을 초래한다.However, in the conventional steam generator, the secondary water supplied to the secondary side to make steam is supplied through filtration and chemical treatment, but it is circulated inside the pipeline and is accompanied by foreign substances and sludge generated through various paths into the steam generator. It is introduced into the tube sheet and tube support plate, or settles on the outer wall of the heat pipe, thereby reducing the heat transfer effect or causing damage.

이를 위하여 유량배분관(8)과 전열관(3) 및 관판(4)의 상태를 확인하기 위하여 카메라가 장착된 내시경을 통하여 확인하는 실정이다.To this end, the situation is confirmed through an endoscope equipped with a camera to check the state of the flow distribution pipe (8), the heat transfer pipe (3) and the tube plate (4).

그러나 이러한 장비는 내시경렌즈와, 이를 수용 및 지지하는 렌즈지지관으로 이루어지므로, 렌즈지지관을 지지하는 수단이 없어 원하는 위치를 찾아 확인할 수 없는 문제점이 있다.However, since such equipment is made of an endoscope lens and a lens support tube for receiving and supporting the same, there is no means for supporting the lens support tube and thus there is a problem in that it cannot find and confirm a desired position.

특히 유량배분관은 형태가 도너츠 형상이어서 중앙의 유량배분홀을 지나서 들어가는 렌즈를 측정자가 원하는 위치로 이동시킬 수 없는 문제점이 있다.In particular, since the flow distribution tube has a donut shape, there is a problem in that the lens that passes through the flow distribution hole in the center cannot move the lens to a desired position.

본 발명은 이를 해결하고자 하는 것으로, 본 발명의 목적은 원자력 발전용 증기발생기의 유량분배관과 관판 사이의 원하는 전열관위치를 찾아 확인 가능토록 하는 검사장치를 제공하려는 것이다.The present invention is to solve this problem, an object of the present invention is to provide an inspection apparatus to find and confirm the desired heat transfer pipe position between the flow distribution pipe and the tube plate of the steam generator for nuclear power generation.

본 발명의 다른 목적은 유량분배관의 위치를 수평과 수직을 지나갈 수 있도록 상태가 수평 및 수직을 이루는 힌지수단과 이를 선택하는 당김수단을 가져서 수평이동과 수직이동을 가능토록 하는 검사장치를 제공하려는 것이다.It is another object of the present invention to provide an inspection apparatus that has horizontal and vertical hinge means and a pulling means for selecting the horizontal and vertical state so that the position of the flow distribution pipe can pass horizontally and vertically. will be.

본 발명의 또 다른 목적은 검사장치를 수평부와 수직부와, 이들의 상태를 조절하는 힌지부로 이루도록 하고, 수평부에는 삽입위치를 알 수 있도록 하는 눈금부 를 설치한 검사장치를 제공하려는 것이다.Still another object of the present invention is to provide an inspection apparatus including a horizontal portion and a vertical portion, and a hinge portion for adjusting the state thereof, and a horizontal portion installed on the horizontal portion so as to know the insertion position.

이를 위하여 본원발명은 원자력발전용 증기발생기의 유량분배관 부근의 전열관 표면 상태를 구석 구석 확인 가능토록 확인용 렌즈와, 렌즈를 지지하는 렌즈지지관과, 렌즈를 포함하는 렌즈지지관을 수용하고 수평부와 수직부가 힌지로 결합된 관체와, 관체의 수직부가 여닫히도록 하는 당김 가이드 로프를 포함하도록 이루어진다.To this end, the present invention accommodates a lens for confirming the corners of the surface of the heat pipe near the flow distribution pipe of the nuclear power generation steam generator, a lens support tube for supporting the lens, and a lens support tube including the lens and is horizontal. And a tubular body in which the part and the vertical part are hinged, and a pulling guide rope for opening and closing the vertical part of the tubular body.

즉, 본 발명은 원자력발전용 증기발생기의 유량분배관 부근의 전열관 표면 상태를 구석 구석 확인 가능토록 하는 확인용 렌즈와, 렌즈를 지지하는 렌즈지지관과, 렌즈를 포함하는 렌즈지지관을 수용하고 수평부와 수직부가 힌지로 결합된 관체와, 관체의 수직부가 수평 및 수직 상태를 이루도록 하는 당김 가이드 로프를 포함하도록 이루어진 원자력발전용 증기발생기의 전열관 표면 검사장치를 제공하려는 것이다.That is, the present invention accommodates a lens for confirming to check corners of the surface of the heat transfer pipe near the flow distribution pipe of the steam generator for nuclear power generation, a lens support tube for supporting the lens, and a lens support tube including the lens. An object of the present invention is to provide a heat pipe surface inspection apparatus for a nuclear power generator steam generator including a tubular body in which the horizontal portion and the vertical portion are hinged, and a pulling guide rope for making the vertical portion of the tubular body horizontal and vertical.

이하 본원발명의 실시예를 도면을 참조하여 상세히 설명한다.Hereinafter, embodiments of the present invention will be described in detail with reference to the drawings.

원자력발전용 증기발생기의 유량분배관 부근의 전열관 표면 상태를 구석 구석 확인 가능토록 하는 확인용 렌즈(37)와, 렌즈(37)를 지지하는 렌즈지지관(38)과, 렌즈(37)를 포함하는 렌즈지지관(38)을 수용하고 수평부(31)와 수직부(32)가 힌지(33)로 결합된 관체(39)와, 관체(39)의 수직부가 수평 및 수직 상태를 이루도록 하는 당김 가이드 로프를 포함하도록 이루어진다.The lens 37 includes a confirmation lens 37 for supporting the identification of the surface of the heat exchanger tube near the flow rate distribution pipe of the nuclear power generation steam generator, a lens support tube 38 for supporting the lens 37, and a lens 37. A tube 39 for accommodating the lens support tube 38 and having a horizontal portion 31 and a vertical portion 32 joined by a hinge 33, and pulling the vertical portion of the tube 39 in a horizontal and vertical state. It is made to include a guide rope.

상기 수평부(31)에는 유량분배판(8)의 중앙을 이루는 유량분배홀(8-1)로의 진입여부를 확인하도록 일정 길이마다 표시한 눈금부(36)를 부가한다.The horizontal portion 31 is provided with a scale 36 marked for each predetermined length to check whether or not to enter the flow distribution hole (8-1) forming the center of the flow distribution plate (8).

상기 수평부(31)에는 가이드로프(34)의 선단을 고정하는 로프고정구(32-1)를 설치한다.The horizontal portion 31 is provided with a rope fixing tool (32-1) for fixing the tip of the guide rope (34).

상기 수직부(32)의 하단은 전열관으로의 위치를 바로 잡을 수 있도록 하는 경사진 절곡부(32-2)를 이룬다.The lower end of the vertical portion 32 forms an inclined bent portion 32-2 to correct the position to the heat transfer pipe.

이를 사용할때는 핸드홀(7)을 따라서 도 7 의 점선상태로 수직부(32)가 수평을 이루도록 사용자가 가이드로프(34)를 당긴다. 이 상태에서 도 4 에 보인 핸드홀(7), 래퍼(20)의 하부 일측에 형성된 통공(22) 및 유량분배판(8)위에서 각 인접하는 전열관(3) 사이를 지나9도 6a 상태), 도 5 에 보인 유량분배판(8)의 유량분배판홀(8-1)을 지나도록 하고(이 경우 내부가 잘 않보일 경우를 대비하여 도 7 에 보인 눈금부(36)를 보고 들어간 깊이를 확인한다), 힌지(33)부분이 유량분배판홀(8-1)을 지나면 가이드로프(34)의 당김을 풀어 도 7 상태와 같이 하중에 의하여 수직부(32)가 수직을 이룬다(도 6b 상태). 그리고 수직부(32)의 하단은 절곡부(32-2)에 의하여 일정 각도로 기울어져 있어, 사용자는 검사 렌즈(37)를 통하여 원하는 전열관(3)표면의 이상 여부를 쉽게 확인토록 한다(도 6c).When using this, the user pulls the guide rope 34 along the handhole 7 so that the vertical portion 32 is horizontal in the dotted state of FIG. 7. In this state, the handhole 7 shown in FIG. 4, the through-hole 22 formed in the lower side of the wrapper 20, and the heat transfer pipes 3 adjacent to each other on the flow distribution plate 8 are in a state of 9 ° 6a), Pass the flow distribution plate hole 8-1 of the flow distribution plate 8 shown in FIG. 5 (in this case, check the depth entered by looking at the scale 36 shown in FIG. 7 in case the inside is not visible well). When the hinge 33 portion passes the flow distribution plate hole 8-1, the guide rope 34 is released and the vertical portion 32 is vertical by load as shown in FIG. 7 (FIG. 6B). . And the lower end of the vertical portion 32 is inclined at an angle by the bent portion 32-2, so that the user can easily check whether the desired surface of the heat transfer tube 3 through the inspection lens 37 (Fig. 6c).

이상과 같이 본원 발명은 원자력 발전용 증기발생기의 유량분배관과 관판 사이의 원하는 전열관위치를 찾아 확인 가능토록 하는 검사장치를 제공한다.As described above, the present invention provides an inspection apparatus for finding and confirming a desired heat transfer pipe position between a flow distribution pipe and a pipe plate of a steam generator for nuclear power generation.

본 발명은 또한 유량분배관의 위치를 수평과 수직을 지나갈 수 있도록 상태 가 수평 및 수직을 이루는 힌지수단과 이를 선택하는 당김수단을 구비하고, 수평이동과 수직이동을 가능토록 하는 검사장치를 제공한다.The present invention also provides an inspection apparatus having a horizontal and vertical hinge means and a pulling means for selecting the same, so that the position of the flow distribution pipe can pass horizontally and vertically, and enables horizontal movement and vertical movement. .

본 발명은 또한 검사장치를 수평부와 수직부와, 이들의 상태를 조절하는 힌지부로 이루도록 하였기에, 수평부에는 삽입위치를 알 수 있도록 하는 눈금부를 설치하여 원하는 위치를 정확하게 확인 가능토록 한다.In the present invention, the inspection device is made up of a horizontal portion and a vertical portion, and a hinge portion for adjusting the state thereof, so that a horizontal portion is provided on the horizontal portion so that the desired position can be accurately identified.

Claims (4)

원자력발전용 증기발생기의 유량분배관 부근의 전열관 표면 상태를 구석 구석 확인 가능토록 하는 확인용 렌즈(37)와, 렌즈(37)를 지지하는 렌즈지지관(38)과, 렌즈(37)를 포함하는 렌즈지지관(38)을 수용하고 수평부(31)와 수직부(32)가 힌지(33)로 결합된 관체(39)와, 관체(39)의 수직부가 수평 및 수직 상태를 이루도록 하는 당김 가이드 로프를 포함하도록 이루어진 것을 특징으로 하는 원자력발전용 증기발생기의 전열관 표면 검사장치.The lens 37 includes a confirmation lens 37 for supporting the identification of the surface of the heat exchanger tube near the flow rate distribution pipe of the nuclear power generation steam generator, a lens support tube 38 for supporting the lens 37, and a lens 37. A tube 39 for accommodating the lens support tube 38 and having a horizontal portion 31 and a vertical portion 32 joined by a hinge 33, and pulling the vertical portion of the tube 39 in a horizontal and vertical state. Heat pipe surface inspection apparatus of the nuclear power generator steam generator characterized in that it comprises a guide rope. 제 1 항에 있어서, 수평부에는 유량분배관으로의 진입여부를 확인하도록 일정 길이마다 표시한 눈금부를 부가한 것을 특징으로 하는 원자력발전용 증기발생기의 전열관 표면 검사장치.2. The heat pipe surface inspection apparatus of a nuclear power generator steam generator according to claim 1, wherein a horizontal portion is provided with a scale mark marked at a predetermined length so as to check whether or not it enters the flow distribution pipe. 제 1 항에 있어서, 수평부에는 가이드로프(34)의 선단을 고정하는 로프고정구(32-1)를 설치한 것을 특징으로 하는 원자력발전용 증기발생기의 전열관 표면 검사장치.2. The heat pipe surface inspection apparatus according to claim 1, wherein a rope fixing tool (32-1) for fixing the tip of the guide rope (34) is provided in the horizontal portion. 제 1 항에 있어서, 수직부(32)의 하단은 전열관으로의 위치를 바로 잡을 수 있도록 하는 경사진 절곡부를 이룬 것을 특징으로 하는 원자력발전용 증기발생기의 전열관 표면 검사장치.2. The heat pipe surface inspection apparatus according to claim 1, wherein the lower end of the vertical portion (32) has an inclined bent portion for correcting the position to the heat pipe.
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KR101702833B1 (en) 2015-10-30 2017-02-08 한국원자력연구원 Apparatus and method for assuring centerline alignment of nuclear steam generator tube and supports
KR20220118177A (en) * 2021-02-18 2022-08-25 주식회사 그린앤텍 Central passageway automatic inspection device for F-type steam generator

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KR101203291B1 (en) 2011-03-07 2012-11-20 한국수력원자력 주식회사 Endoscope guide for visual inspection of nuclear steam generator
KR101721938B1 (en) 2015-06-22 2017-04-04 이노스웰(주) A monitoring device for welding parts of a steam generator

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JP3165630B2 (en) * 1995-12-07 2001-05-14 三菱重工業株式会社 Traveling temperature measurement and visual inspection device
WO1997050005A2 (en) 1996-06-14 1997-12-31 R. Brooks Associates, Inc. Inspection device

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KR101702833B1 (en) 2015-10-30 2017-02-08 한국원자력연구원 Apparatus and method for assuring centerline alignment of nuclear steam generator tube and supports
KR20220118177A (en) * 2021-02-18 2022-08-25 주식회사 그린앤텍 Central passageway automatic inspection device for F-type steam generator

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